Search Results - "Kudinov, Pavel"

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  1. 1

    CFD simulation of thermal stratification and mixing in a Nordic BWR pressure suppression pool by Wang, Xicheng, Acharya, Govatsa, Grishchenko, Dmitry, Kudinov, Pavel

    Published in Nuclear engineering and technology (01-12-2024)
    “…Boiling Water Reactor (BWR) employs the Pressure Suppression Pool (PSP) as a heat sink to prevent overpressure of the reactor vessel and containment. Steam can…”
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    Journal Article
  2. 2

    Steam generator leakage in lead cooled fast reactors: Modeling of void transport to the core by Jeltsov, Marti, Villanueva, Walter, Kudinov, Pavel

    Published in Nuclear engineering and design (01-03-2018)
    “…•Gas transport during SGTL is analyzed using Lagrangian-Eulerian CFD approach.•Probabilistic-deterministic approach is used to analyze LFR primary system…”
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    Journal Article
  3. 3

    Development of scaling approach based on experimental and CFD data for thermal stratification and mixing induced by steam injection through spargers by Wang, Xicheng, Grishchenko, Dmitry, Kudinov, Pavel

    Published in Nuclear engineering and technology (01-03-2024)
    “…Advanced Pressurized Water Reactors (APWRs) and Boiling Water Reactors (BWRs) employ a suppression pool as a heat sink to prevent containment overpressure…”
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    Journal Article
  4. 4

    Analysis of the Effect of Severe Accident Scenario on Debris Properties in Lower Plenum of Nordic BWR Using Different Versions of MELCOR Code by Galushin, Sergey, Kudinov, Pavel

    “…Nordic Boiling Water Reactors (BWRs) employ ex-vessel debris coolability as a severe accident management strategy (SAM). Core melt is released into a deep pool…”
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    Journal Article
  5. 5

    Coupled thermo-mechanical creep analysis for boiling water reactor pressure vessel lower head by Villanueva, Walter, Tran, Chi-Thanh, Kudinov, Pavel

    Published in Nuclear engineering and design (01-08-2012)
    “…► We consider a severe accident in a BWR with melt pool formation in the lower head. ► We study the influence of pool depth on vessel failure mode with creep…”
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    Journal Article Conference Proceeding
  6. 6

    Approach and Development of Effective Models for Simulation of Thermal Stratification and Mixing Induced by Steam Injection into a Large Pool of Water by Li, Hua, Kudinov, Pavel, Villanueva, Walter

    “…Steam venting and condensation in a large pool of water can lead to either thermal stratification or thermal mixing. In a pressure suppression pool (PSP) of a…”
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    Journal Article
  7. 7

    Scenario Grouping and Classification Methodology for Postprocessing of Data Generated by Integrated Deterministic-Probabilistic Safety Analysis by Galushin, Sergey, Kudinov, Pavel

    “…Integrated Deterministic-Probabilistic Safety Assessment (IDPSA) combines deterministic model of a nuclear power plant with a method for exploration of the…”
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    Journal Article
  8. 8

    Validation of Effective Models for Simulation of Thermal Stratification and Mixing Induced by Steam Injection into a Large Pool of Water by Laine, Jani, Puustinen, Markku, Villanueva, Walter, Li, Hua, Kudinov, Pavel

    “…The Effective Heat Source (EHS) and Effective Momentum Source (EMS) models have been proposed to predict the development of thermal stratification and mixing…”
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    Journal Article
  9. 9

    Prediction of Flow Regimes and Thermal Hydraulic Parameters in Two-Phase Natural Circulation by RELAP5 and TRACE Codes by Phung, Viet-Anh, Kudinov, Pavel

    “…In earlier study we have demonstrated that RELAP5 can predict flow instability parameters (flow rate, oscillation period, temperature, and pressure) in single…”
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    Journal Article
  10. 10

    Input Calibration and Validation of RELAP5 Against CIRCUS-IV Single Channel Tests on Natural Circulation Two-Phase Flow Instability by Rohde, Martin, Grishchenko, Dmitry, Kudinov, Pavel, Phung, Viet-Anh

    “…RELAP5 is a system thermal-hydraulic code that is used to perform safety analysis on nuclear reactors. Since the code is based on steady state, two-phase flow…”
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    Journal Article
  11. 11

    The Effective Convectivity Model for Simulation of Molten Metal Layer Heat Transfer in a Boiling Water Reactor Lower Head by Tran, Chi-Thanh, Kudinov, Pavel

    “…This paper is concerned with the development of approaches for assessment of core debris heat transfer and Control Rod Guide Tube (CRGT) cooling effectiveness…”
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    Journal Article
  12. 12

    Analysis of the effect of MELCOR modelling parameters on in-vessel accident progression in Nordic BWR by Galushin, Sergey, Kudinov, Pavel

    Published in Nuclear engineering and design (15-08-2019)
    “…•The effect of epistemic uncertainty in MELCOR models was studied using Morris method.•Major contributors to the uncertainty in the MELCOR code predictions…”
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    Journal Article
  13. 13

    Simulation of jets induced by steam injection through multi-hole sparger using effective heat and momentum models by Wang, Xicheng, Grishchenko, Dmitry, Kudinov, Pavel

    Published in Nuclear engineering and design (15-04-2023)
    “…•Effective heat and momentum source models for steam injection through multi-hole sparger.•High intensity of the turbulence induced by steam condensation in…”
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    Journal Article
  14. 14

    Sensitivity and uncertainty analysis of the vessel lower head failure mode and melt release conditions in Nordic BWR using MELCOR code by Galushin, Sergey, Kudinov, Pavel

    Published in Annals of nuclear energy (01-01-2020)
    “…•Vessel breach due to penetration failure is predicted to occur first by MELCOR code.•User defined solid debris ejection mode has the dominant effect on MELCOR…”
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    Journal Article
  15. 15

    Sensitivity analysis of debris properties in lower plenum of a Nordic BWR by Galushin, Sergey, Kudinov, Pavel

    Published in Nuclear engineering and design (01-06-2018)
    “…•The effect of MELCOR modelling parameters on in-vessel accident progression.•Sensitivity analysis of in-vessel accident progression and debris properties.•The…”
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    Journal Article
  16. 16

    Analysis of core degradation and relocation phenomena and scenarios in a Nordic-type BWR by Galushin, Sergey, Kudinov, Pavel

    Published in Nuclear engineering and design (15-12-2016)
    “…•A data base of the debris properties in lower plenum generated using MELCOR code.•The timing of safety systems has significant effect on the relocated debris…”
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    Journal Article
  17. 17

    Implementation of framework for assessment of severe accident management effectiveness in Nordic BWR by Galushin, Sergey, Grishchenko, Dmitry, Kudinov, Pavel

    Published in Reliability engineering & system safety (01-11-2020)
    “…•Probabilistic framework for risk assessment has been developed and implemented.•The framework employs iterative processes of knowledge refinement.•Treatment…”
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    Journal Article
  18. 18

    Pre-test analysis for definition of steam injection tests through multi-hole sparger in PANDA facility by Wang, Xicheng, Grishchenko, Dmitry, Kudinov, Pavel

    Published in Nuclear engineering and design (01-01-2022)
    “…•Effective heat and momentum source models for steam injection into a pool.•Development of thermal stratification and mixing in a large water pool.•Formation…”
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    Journal Article
  19. 19

    On the need for conjugate heat transfer modeling in transient CFD simulations by Papukchiev, Angel, Grishchenko, Dmitry, Kudinov, Pavel

    Published in Nuclear engineering and design (01-10-2020)
    “…•CFD models with and without solid structures are generated.•Two different TALL-3D experiments are calculated with both CFD models.•Comparative analyses are…”
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    Journal Article
  20. 20

    Momentum induced by steam injection into a subcooled pool by Wang, Xicheng, Kudinov, Pavel, Grishchenko, Dmitry, Puustinen, Markku, Räsänen, Antti, Kotro, Eetu, Pyy, Lauri

    “…•Momentum rate induced by steam injection into a subcooled water is measured.•Correlation for condensation regime coefficient by Jakob and Mach numbers.•Rapid…”
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    Journal Article